ML20206N207
| ML20206N207 | |
| Person / Time | |
|---|---|
| Site: | LaSalle |
| Issue date: | 04/30/1999 |
| From: | Shaun Anderson, Jamie Benjamin COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9905170168 | |
| Download: ML20206N207 (9) | |
Text
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3 commonweanh a.tinon company l
lealle Generating At.ition 2 Nil North 21st Roatl 51arscilles. II. 61.4 i l N'5' l
Tel 815 45'C61 Comed l
May 10,1999 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units 1 and 2 I
Facility Operating License Nos. NPF-11 and NPF-18
{
NRC Docket Nos. 50-373 and 50-374
Subject:
Monthly Performance Report for April,1999 Enclosed is the LaSalle County Station Monthly Performance Report for the month of April,1999.
Should you have any questions conceming this letter, please contact Frank A. Spangenberg, Ill, Regulatory Assurance Manager, at (815) 357-6761, extension 2383.
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La le County Station Enclosure r
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Regional Administrator - NRC Region ill 3
i NRC Senior Resident Inspector - LaSalle County Station 4U j
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9905170168 990430 I
DR ADOCK 05000373 I
von A 1 ' nit i Dil) ( a slit lLtO) w
LASALLE COUNTY STATION
' UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 50-373 NRC DOCKET NO. 50-374 LICENSE NO. NPF-11 LICENSE NO. NPF-18 t
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1 TABLE OF CONTENTS i
1.
Monthly Report for LaSalle Unit One A. Operating Data Summary B. Unit Shutdowns and Operating Summary C. Unique Reporting Requirements ll.
Monthly Report for LaSalle Unit Two A. Operating Data Summary B. Unit Shutdowns and Operating Summary.
C. Unique Reporting Requirements j
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- Monthly Report for LaSalle County Station Unit One-April,1999 A. OPERATING DATA
SUMMARY
FOR UNIT ONE DOCKET NO.:
50-373 UNIT:
LaSalle One DATE:
May 4,1999 COMPLETED BY:
S. Anderson TELEPHONE:
(815) 357-6761 x2620
- 1. Reporting Period: April,1999 Gross Hours: 719
- 2. Currently Authorized Power Level: 3,323 (MWt)
Design Electrical Rating: 1,078 (MWe-net)
Max Dependable Capacity: 1,036 (MWe-net)
- 3. Power Level To Which Restricted (If Any): None
- 4. Reasons For Restriction (if Any): N/A THIS MONTH YEAR-TO-DATE CUMULATIVE 5.
Reactor Cntical Hours 719 2,879 85,002.9 6.
Reactor Reserve 0.0 0.0 1,641.2 l
Shutdown Hours 7.
Hours Generator On-719 2,879 82,892.6 Une 8.
Unit Reserve 0.0 0.0 1.0 Shutdown Hours 9.
Gross Thermal 2,303,182 9,436,814 248,116,164 Energy (MWHt) 10.
Gross Electric Energy 786,576 3,227,604 83,089,855_
(MWHe) 11.
Net Electrical Energy 765,617 3,148,739 80,154,865 (MWHe) i 12.
Reactor Service 100.0 100.0 63.2 Factor (%)
13.
Reactor Availability 100.0 100.0 64.5 Factor (%)
14.
Unit Service Factor 100.0 100.0 61.7
(%)
15.
Unit Availability 100.0 100.0 61.7 Factor 16.
Unit Capacity Factor 102.8 105.6 57.6 (MDC) 17.
Unit Capacity Factor 98.8 101.5 55.3 (design MWe) 18.
Unit Forced Outage 0.0 0.0 13.8 Factor (%)
- 19. Shutdowns Scheduled Over Next 6 Months:
L1R08 - October 23,1999
- 20. If Shutdown at End of Report Period, Date of Startup: N/A
B. UNIT SHUTDOWNS AND OPERATING
SUMMARY
REPORT MONTH ~ APRIL 1999 NO DATE TYPE (1)
DURATION REASON METHOD OF CORRECTIVE ACTIONS /
(HOURS)*
(2)
SHUTTING COMMENTS DOWN REACTOR (3)
None 1
SUMMARY
Unit 1 began the month in a short downpower for Control Rod exercising. The downpower continued for the first 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of April, as the unit ramped up to 100% power.
Ths Unit then operated at 100% power until late on April 2,1999, when power was reduced to support flux tilt t: sting performed to identify a leaking fuel bundle. This downpower lasted 3 days and 5 hot'rs. The leaking fu:1 bundle was successfully identified and has been suppressed by the insertion of adjacent control rods.
The Unit returned to 100% power early on April 6,1999 and operated at 100% power for the remainder of the month, with the exception of three short downpowers.
Tha first two downpowers were performed April 11,1999 and April 18,1999 for Control Rod pattern adjustments. These downpowers lasted 7 and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, respectively. Due to the suppression cf the leaking fu:1 bundle, the ramp rate back to 100% power following these downpowers was slower than normal. This had the effect of extending the ramps to 100% power by approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Th3 third downpower was performed on Ap0 25,1999 in support of monthly surveillance testing. This downpower was scheduled to last approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, but was extended for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> due to problems with ths Reactor Recirculation systcm Flow Control Valve Hydraulic Power Units (HPU). The problem was id:ntified as a failed solenoid valve coil. The failed solenoid valve was replaced and the Unit returned to 100%
power at approximately 1600 on April 25,1999.
Ycar-to-date forced outage hours = 0.0 Cumulative forced outage hours = 13,227.8 TABLE KEY:
(1)
(3)
F: Forced Method:
S: Scheduled
- 1. Manual
- 2. Manual Scram (2)
- 3. Automatic Scram Reason:
- 4. Continca%i.
A Equipment Failure (Explain)
- 5. Other (Explain)
B Maintenance or Test C Refueling D Regulatory Restriction E Operator / Licensing Exam F Administrative G Operational Error (Explain)
H Other (Explain)
9 Cl UNIQUE REPORTING REQUIREMENTS FOR UNIT ONE
- 1. Challenges other than routine surveillance testing to Safety / Relief Valve Operations--None
- 2. Major Changes to Radioactive Waste Treatment System--None
- 3. Off-S'*o Dose Calculation Manual Changes--None
)
i
r 4
til Monthly Report for LaSalle County Station Unit Two-April,1999 A. OPERATING DATA
SUMMARY
FOR UNIT TWO DOCKET NO.:
50-374 UNIT:
LaSalle Two DATE:
May 4,1999 COMPLETED BY:
S. Anderson TELEPHONE:
(815) 357-6761 x2620
- 1. Reporting Period: April,1999 Gross Hours: 719
- 2. Currently Authorized Power Level: 3,323 (MWt)
Design Electrical Rating: 1,078 (MWe-net)
Max Dependable Capacity: 1,036 (MWe-net)
- 3. Power Level To Which Restricted (If Any): None
- 4. Reasons For Restriction (If Any): N/A THIS MONTH YEAR-TO-DATE CUMULATIVE 5.
Reactor Critical Hours 510.8 510.8 77,539.2 6.
Reactor Reserve 0.0 0.0 1,716.9 Shutdown Hours 7.
Hours Generator On-468.6 468.6 76,438.8 Line 8.
Unit Reserve 0.0 0.0 0.0 Shutdown Hours 9.
Gross Therrnal 1,299,205 1,299,205 231,821,892 Energy (MWHt) 10.
Gro?s Electric Energy 438,666 438,666 77,614,590 (MWHe) 11.
Net Electrical Energy 421,895 421,895 74,395,538 (MWHe) 12.
Reactor Service 71.0 17.7 60.9 Factor (%)
13.
Reactor Availability 71.0 17.7 62.2 Factor (%)
14.
Unit Service Factor 65.2 16.3 60.0
(%)
15.
Unit Availability 65.2 16.3 60.0 Factor 16.
Unit Capacity Factor 56.6 14.1 56.4 (MDC) 17.
Unit Capacity Factor 54.4 13.6 54.2 (desion MWe) 18.
Unit Forced Outage 34.9 83.7 19.7 Factor (%)
- 19. Shutdowns Scheduled Over Next 6 Months: None
- 20. If Shutdown at End of Report Period, Date of Startup: N/A
t B. UNIT SHUTDOWNS AND OPERATING
SUMMARY
REPORT MONTH APRIL 1999 NO DATE TYPE DURATION REASON (2)
METHOD OF CORRECTIVE ACTIONS /
(1)
(HOURS)*
SHUTTING COMMENTS DOWN REACTOR (3) 07 98/01/01 F
251.2 C
2 Following the lifting of Confirmatory Action Letter Rlll-96-008, L2RO7 is considered a forced extension of a refueling l
outage.
Year-to-date forced outage hours = 2,411.2 Cumulative forced outage hours = 18,803 5 TABLE KEY:
(1)
(3)
F: Forced Method:
S: Scheduled
- 1. Manual
- 2. Manual Scram (2)
- 3. Autematic Scram Reason:
- 4. Continuation A Equipment Failure (Explain)
- 5. Other (Explain)
B Maintenance or Test C Refueling D Regulatory Restriction E Operator / Licensing Exam F Administrative G Operational Error (Explain)
H Other (Explain)
SUMMARY
Unit 2 began the month of April shutdown in a forced extension of refueling outage L2R07. Startup activities b:gan on April 9,1999. The mode switch was taken to the startup position at 14:10. Criticality was achieved at 17:10. The generator was first placed on line at 12:13 on April 11,1999. Following turbine trip testing, the g:n rator was again placed on line at 18:49 on April 11,1999. Power ascension continued until 100% reactor pow r was achieved at 14:40 on April 17,1999.
Two short downpowers were performed on April 18,1999 and April 19,1999 for Control Rod pattern cdjustments. These downpowers lasted 3 and a half and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, respectively.
Tha unit then operated at full power until a downpower on April 22,1999. This downpower was performed for Control Rod pattern adjustments and to support a test of the Unit 2 Motor Driven Reactor Feedwater Pump (MDRFP). The scheduled activities were completed in approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but return to full power was d: layed for approximately 12 and a half hours due to Turbine Generator (TG) differential expansion cdministrative limitations. A General Electric evaluation of TG performance during this downpower resulted in changes to the TG differential expansion administrative limits that allowed the unit to return to full power. The total duration of this downpower was 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />.
Tha unit then operated at full power until a short downpower was performed on April 27,1999. This downpower was performed to ensure thermal limits would not be violated while restoring a control rod which
r tripla-notched in
SUMMARY
- (Continued) ths insert direction during control rod exercising. The downpower approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Thermal limits were v::rified prior to returning to full power.
Th3 unit then operated at full power until a downpower was initiated at 22:00 on April 30,1999 to support Condenser tube leak checks.
C. UNIQUE REPORTING REQUIREMENTS FOR UNIT TWO
- 1. Challenges other than routine surveillance testing to Safety / Relief Valve Operations--None
- 2. Major Changes to Radioactive Waste Treatment Systems--None
- 3. Off-Site Dose Calculation Manual Changes--None